SAMCEP: An Application of Correlated Monte Carlo to the Simultaneous Solution of Multiple, Perturbed, Time-Dependent Neutron Transport Problems in Complex Three-Dimensional Geometry.
Final rept. 1 Dec 70-1 Dec 71
MATHEMATICAL APPLICATIONS GROUP INC WHITE PLAINS N Y
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SAMCEP is a system of U.S.A.-Standard FORTRAN programs for the solution by Monte Carlo of several correlated neutron transport problems in complex three-dimensional geometries. Up to 10 correlated problems, involving up to 100 perturbations, of composition, neutron cross sections, angular or energy distributions, andor source spectra, can be run simultaneously. Individual problem fluxes or doses region-, energy-, and on option time-dependent, as well as the differences between those of any or all pairs of problems, are available. SAMCEP retains essentially all the features of its predecessor code, SAMCE, including the use of basic neutron data in the latest ENDFB format. Author
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- Fission Reactor Physics